Engineering design and control scenario for steady-state high-beta operation in National Centralized Tokamak

K. Tsuchiya, M. Akiba, H. Azechi, T. Fujii, T. Fujita, M. Fujiwara, K. Hamamatsu, H. Hashizume, N. Hayashi, H. Horiike, N. Hosogane, M. Ichimura, K. Ida, Y. Ikeda, T. Imai, N. Inoue, S. Ishida, S. Itoh, Y. Kamada, H. KawashimaM. Kikuchi, A. Kimura, K. Kizu, H. Kubo, Y. Kudo, K. Kurihara, G. Kurita, M. Kuriyama, K. Masaki, M. Matsukawa, M. Matsuoka, Y. Miura, Y. M. Miura, N. Miya, A. Morioka, K. Nakamura, H. Ninomiya, A. Nishimura, K. Okano, K. Okuno, A. Sagara, M. Sakamoto, S. Sakurai, K. Sato, R. Shimada, A. Shimizu, T. Suzuki, H. Takahashi, Y. Takase, M. Takechi, H. Tamai, S. Tanaka, H. Tsutsui, Y. Uesugi, K. Yatsu, N. Yoshida

研究成果: Contribution to journalConference article査読

1 被引用数 (Scopus)

抄録

The mission of the National Centralized Tokamak (NCT) is to establish high-beta steady-state plasma operation for DEMO and to contribute to ITER. Plasma performance with high-beta conditions is discussed. It is found that near break-even class plasma (QDTeq≥0.7) with high beta (βN ≥ 3.5) is achievable with 25 MW of NB power at IP = 4.0 MA and an aspect ratio of 2.6. High beta with steady-state full current drive is possible with 13 MW of NB power at IP = 1.5-1.7 MA. In the engineering design activity of NCT, the strength of the support structure and strength of material for the conductor is confirmed for the superconducting coils, and the successful progress of R&D of boron-loaded resin for neutron shielding is discussed.

本文言語英語
ページ(範囲)1599-1605
ページ数7
ジャーナルFusion Engineering and Design
81
8-14 PART B
DOI
出版ステータス出版済み - 2 2006
イベントProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B -
継続期間: 5 22 20055 27 2005

All Science Journal Classification (ASJC) codes

  • 土木構造工学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 機械工学

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